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Frontiers in Energy

ISSN 2095-1701

ISSN 2095-1698(Online)

CN 11-6017/TK

邮发代号 80-972

2019 Impact Factor: 2.657

Frontiers of Energy and Power Engineering in China  2008, Vol. 2 Issue (4): 471-474   https://doi.org/10.1007/s11708-008-0074-6
  本期目录
Oxidation performance of graphite material in reactors
Oxidation performance of graphite material in reactors
LUO Xiaowei, YU Xinli, YU Suyuan
Institute of Nuclear Energy and New Energy Technology, Tsinghua University
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Abstract:Graphite is used as a structural material and moderator for high temperature gas-cooled reactors (HTGR). When a reactor is in operation, graphite oxidation influences the safety and operation of the reactor because of the impurities in the coolant and/or the accident conditions, such as water ingress and air ingress. In this paper, the graphite oxidation process is introduced, factors influencing graphite oxidation are analyzed and discussed, and some new directions for further study are pointed out.
出版日期: 2008-12-05
 引用本文:   
. Oxidation performance of graphite material in reactors[J]. Frontiers of Energy and Power Engineering in China, 2008, 2(4): 471-474.
LUO Xiaowei, YU Xinli, YU Suyuan. Oxidation performance of graphite material in reactors. Front. Energy, 2008, 2(4): 471-474.
 链接本文:  
https://academic.hep.com.cn/fie/CN/10.1007/s11708-008-0074-6
https://academic.hep.com.cn/fie/CN/Y2008/V2/I4/471
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